Authors & Affiliations
Askhadullin R.Sh., Legkikh A.Yu., Simakov A.A.
A.I. Leypunsky Institute for Physics and Power, Obninsk, Russia
Abstract
The most perspective heavy liquid metal coolants (HLMC) are currently the lead and eutectic alloy 44,5% Pb - 55.5% Bi. In order to ensure corrosion protection of structural steel in the process of operation facilities with HLMC is necessary to maintain dissolved oxygen in the given range. The most promising method to maintain a given oxygen regime in HLMC is a solid-phase method of regulating the oxygen thermodynamic activity, developed at the SSC RF – IPPE. Means of the method implementation are the mass-transfer apparatus (MA), in which filling pellets of lead oxide (PbO) is used as the source of oxygen. The pellets are made from lead oxide powder by special technology and placed in the reaction vessel MA. The principle of operation MA based on the process dissolution of lead oxide granules in HLMC. When dissolved oxides is enriched with oxygen HLMC. For the design of mass-transfer apparatus is an important knowledge of the hydraulic resistance of the lead oxide granular layer in the flow of HLMC. The value of the hydraulic resistance is the determining factor in selecting circulator of MA and, largely, the geometric parameters of the device. The paper presents the results of experimental studies to determine the hydraulic resistance of the lead oxide granular layer in the flow of lead-bismuth coolant. The studies were performed on circulation loop with lead-bismuth coolant «TT-2M» (SSC RF – IPPE). On the basis of obtained experimental data the proposed dependence for the calculation of the hydraulic resistance coefficient of lead oxide granular layer. The resulting dependence can be used to estimate hydraulic characteristics of the reaction vessel during the development of mass-transfer apparatus for industrial and research facilities with HLMC.
Keywords
hydraulic resistance, oxygen, mass-transfer apparatus, lead oxide, flow, dissolution, lead-bismuth, solid-phase method, coolant, experiment
Article Text (PDF, in Russian)
UDC 621.039.534.6
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants", issue 1, 2014